新版R.G.1.20《预运行和初始启动试验期间堆内构件振动综合评价大纲》增补的要求简述

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Requirement Description for R.G.1.20 Addenda ‘Comprehensive Vibration Assessment Program for Reactor Internals During Preoperational and Initial Startup Test’

Shanghai Nuclear Engineering Research and Design Institute, Shanghai, 200233, China

摘要: 美国核安全管理委员会(NRC)在2007年发布了新版R.G.1.20《预运行和初始启动试验期间堆内构件振动综合评价大纲》。本文对新版R.G.1.20的编制背景进行了说明,对新版增补的主要内容,包括流致振动分析中采用计算流体动力学(CFD)进行必要的附加分析及对主蒸汽管系(包括管线、阀与干燥器等)声共振问题的评价等要求进行了阐述,通过例举一些典型的流致振动失效原因分析案例说明新版R.G.1.20对核电厂安全运行的重要意义。
- 堆内构件 /
- 振动综合评价大纲 /
- 增补要求
Abstract: The new revision of R.G.1.20 ’Comprehensive Vibration Assessment Program for Reactor Internals during Preoperational and Initial Startup Test’ was issued by NRC in 2007.In this paper,the back-ground for the new revision of R.G.1.20 is demonstrated.Major notes of addenda are stated in contrast with the former revision,including CFD analysis and supplementary analysis in flow-induced vibration analysis,and evaluation requirement for acoustic resonance problem of main steam system（pipe line,relief valve and dryer）.Some typical examples are presented for flow-induced vibration failure cause.It’s shown that the new comprehensive vibration assessment program is crucial for the safety operation and economics in nuclear power plants.
- Reactor internals /
- Comprehensive vibration assessment program /
- Addenda requirement